Master curve characterization of the fracture toughness behavior in SA508 Gr.4N low alloy steels
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference28 articles.
1. K. Suzuki, J. Nucl. Mater. 108&109 (1982) 443.
2. Application of intercritical heat treatment to improve toughness of SA508 Cl.3 reactor pressure vessel steel
3. Effects of carbide precipitation on the strength and Charpy impact properties of low carbon Mn–Ni–Mo bainitic steels
4. Master curve techniques to evaluate an irradiation embrittlement of nuclear reactor pressure vessels for a long-term operation
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